FISSILE AND FUSILE BREEDING IN THE THORIUM FUSION FISSION HYBRID
|
|
- Melinda Sims
- 6 years ago
- Views:
Transcription
1 Proceedings of the 1 st International Nuclear and Renewable Energy Conference (INREC10), Amman, Jordan, March 21-24, 2010 FISSILE AND FUSILE BREEDING IN THE THORIUM FUSION FISSION HYBRID Magdi Ragheb and Ayman Nour Eldin Department of Nuclear, Plasma and Radiological Engineering University of Illinois at Urbana-Champaign, 216 Talbot Laboratory, 104 South Wright Street, Urbana, Illinois 61801, USA. mragheb@illinois.edu, anourel2@illinois.edu ABSTRACT The thorium fuel cycle fissile and fusile breeding in a molten salt and a solid fuel blanket for a system consisting of fusion fuel factories coupled to fission satellites burners, is considered. The use of the thorium cycle in a fusion fission hybrid could bypass the stage of fourth generation fission breeder reactors in that the energy multiplication in the fission island allows the satisfaction of energy breakeven and the Lawson condition in magnetic and inertial fusion reactor experiments, hence an early introduction of fusion energy. The nuclear performance of a fusion-fission hybrid reactor having a molten salt composed of Na-Th-F-Be as the blanket fertile material and operating with a catalyzed or a semi-catalyzed Deuterium-Deuterium (DD) plasma is compared to a system with a Li-Th-F-Be salt operating with a Deuterium-Tritium (DT) plasma. In a fusion reactor with a 42-cm thick salt blanket followed by a 40-cm thick graphite reflector, the catalyzed DD system exhibits a fissile nuclide production rate of 0.88 Th(n, γ) reactions per fusion source neutron. The DT system, in addition to breeding tritium from lithium for the DT reaction yields 0.74 Th(n, γ) breeding reactions per fusion source neutron. Even though both approaches provide substantial energy amplification through the fusion-fission coupling process, the DT system possesses marginal tritium breeding in the fusion island of triton / source neutron and would need supplemental breeding in the fission satellites to reach a value of unity. Neutron multiplication and flux trap strategies are needed to maximize the fusile breeding aspects. In a solid enrichment factory approach using a flux trap concept and lead as a neutron multiplier to maximize breeding, a tritium yield per source neutron above unity of 1.08 and a Th (n, γ) reaction yield of 0.4 can be obtained for the DT fusion plasma in a concept where ThO 2 Zircaloyclad fuel assemblies for Light Water Reactors (LWRs) are enriched in the U 2 isotope. This corresponds to 0.77kg/[MW(th).year] of fissile fuel production, and 1.94 years of irradiation in the fusion reactor to attain an average w/o fissile enrichment in the fuel assemblies. 1. INTRODUCTION With the present day availability of fissile U 25 and Pu 29, and available fusion and accelerator neutron sources, a fresh look at the Thorium-U 2 fuel cycle is warranted. The use of the thorium cycle in a fusion fission hybrid could bypass the stage of fourth generation breeder reactors in that the energy multiplication in the fission part allows the satisfaction of energy breakeven and the Lawson condition in magnetic and inertial fusion reactor designs. This allows for the incremental development of the technology for the eventual introduction of a pure fusion technology [1-10]. 2. ADVANTAGES OF THE THORIUM FUEL CYCLE The following advantages of the thorium fuel cycle over the U 25 -Pu 29 fuel cycle can be enumerated [11-17]: 1. Breeding is possible in both the thermal and fast parts of the neutron spectrum with a regeneration factor of η > 2 (Fig. 1). Figure 1: Regeneration factor as a function of neutron energy for the different fissile isotopes. NINREC10-1
2 2. Expanded nuclear fuel resources due to the higher abundance of the fertile Th 22 than U 28. The USA proven resources in the state of Idaho amount to 600,000 tons of 0 percent of Th oxides. The probable reserves amount to 1.5 million tons. There exists about,000 tons of already milled thorium in a USA strategic stockpile stored in Nevada.. Lower nuclear proliferation concerns due to the reduced limited needs for enrichment of the U 25 isotope that is needed for starting up the fission cycle and can then be later replaced by the bred U 2. The fusion fission fusion hybrid totally eliminates that need. 4. A superior system of handling fission products wastes than other nuclear technologies and a much lower production of the long lived transuranic elements as waste. One ton of natural Th 22, not requiring enrichment, is needed to power a 1,000 MWe reactor per year compared with about tons of uranium solid fuel to produce the same amount of power. The thorium just needs to be purified then converted into a fluoride. The same initial fuel loading of one ton per year is discharged primarily as fission products to be disposed of for the fission thorium cycle. 5. Ease of separation of the lower volume and short lived fission products for eventual disposal. 6. Higher fuel burnup and fuel utilization than the U 25 -Pu 29 cycle. 7. Enhanced nuclear safety associated with better temperature and void reactivity coefficients and lower excess reactivity in the core. 8. With a tailored breeding ratio of unity, a fission thorium fuelled reactor can generate its own fuel, after a small amount of fissile fuel is used as an initial loading. 9. The operation at high temperature implies higher thermal efficiency with a Brayton gas turbine cycle instead of a Joule or Rankine steam cycle, and lower waste heat that can be used for desalination or space heating. An open air cooled cycle can be contemplated eliminating the need for cooling water and the associated heat exchange equipment in arid areas of the world. 10. A thorium cycle for base-load electrical operation would provide a perfect match to peak-load cycle wind turbines generation. The produced wind energy can be stored as compressed air which can be used to cool a thorium open cycle reactor, substantially increasing its thermal efficiency, yet not requiring a water supply for cooling. 11. The unit powers are scalable over a wide range for different applications such as process heat or electrical production. Units of 100 MWe each can be designed, built and combined for larger power needs. 12. Operation at atmospheric pressure without pressurization implies the use of standard equipment with a lower cost than the equipment operated at high pressure in the LWRs cycle.. FUSION ISLAND CONSIDERATIONS For an immediate application of the fusion hybrid using the Th cycle, the DT fusion fuel cycle can be used: D + T He (.52 MeV)+ n (14.06 MeV) MeV (1) The tritium would have to be bred from the abundant supplies of lithium using the reactions with its two isotopes: Li + n (thermal) He (2.05 MeV)+ T (2.7 MeV) MeV He + n + T MeV Li + 0n (fast) In this case a molten salt containing Li for tritium breeding as well as Th for U 2 breeding can be envisioned: LiF. BeF2. ThF 4 For a practically unlimited supply of deuterium from water at a deuterium to hydrogen ratio of D/H = 150 ppm in the world oceans, one can envision the use of the catalyzed DD reaction in the fusion island: D + 1D 1T (1.01) + 1H (.0) MeV D + 1D 2He (0.82) + 0n (2.45) +.27 MeV D + 1T 2He (.52) + 0n (14.06) MeV D + 2He 2He (.67) + 1H (14.67) MeV D 21H + 2 2He + 2 0n + 4.2MeV () with each of the six deuterons contributing an energy release of 4.2 / 6 = MeV. For plasma kinetic reactions temperatures below 50 kev, the DHe reaction is not significant and the energy release would be = with each of the five deuterons contributing an energy release of 24.89/5 = MeV. D + D T (1.01) + H (.0) MeV D + D He (0.82) + n (2.45) +.27 MeV D + T He (.52) + n (14.06) MeV (4) 5 D H + He + He + 2 n MeV In this case, there would be no need to breed tritium, and the lithium can be replaced by Na in a molten salt with the following composition: NaF. BeF2. ThF 4 (2) NINREC10-2
3 of: With a density and percentage molecular composition gm ρ = 4.52,( mol %) cm 4. FUSION FISSION HYBRID LIQUID METAL THORIUM BREEDER A system consisting of fusion fuel factories using DT or Catalyzed DD fusion and fission satellites receiving the bred fissile fuel for burning is shown in Fig. 2. A one dimensional calculational model considers a plasma cavity with a 150 cm radius. The plasma neutron source is uniformly distributed in the central 100 cm radial zone and is isolated from the first structural wall by a 50 cm vacuum zone (Table 1). The blanket module consists of a 1 cm thick Type 16 stanless steel first structural wall that is cooled by a 0.5 cm thick water channel, a 42 cm thick molten salt filled energy absorbing and breeding compartment, and a 40 cm thick graphite neutron reflector (Table 2). The molten salt and graphite are contained within 1 cm thick Type 16 stainless steel structural shells 5. BREEDING IN MOLTEN SALT Computations were conducted using the one dimensional Discrete Ordinates transport ANISN code with a P Legendre expansion and an S 12 angular quadrature. The catalyzed DD system exhibits a fissile nuclide production rate of Th(n, γ) reactions per fusion source neutron. The DT system, in addition to breeding tritium from lithium for the DT reaction yields 0.77 Th(n, γ) breeding reactions per fusion source neutron. Even though both approaches provide substantial energy amplification through the fusion-fission coupling process, the DT system possesses marginal tritium breeding in the fusion island of triton per source neutron and would need supplemental breeding in the fission satellites to reach a value of unity (Table ). The largest Th(n,γ) reaction rate (0.966) occurs when the sodium salt is used in conjunction with the DT reaction. For this case, however, the tritium required to fuel the plasma must be supplied to the system, since that produced in the blanket would be negligible (.18x10 - ). A system of such kind has been proposed and studied by Blinken and Novikov [1]. D Li U 2 Li DT Fusion U 2 Fission T Th 22 T D Catalyzed DD Fusion U 2 U 2 Fission Th 22 Figure 2. Material flows in the DT (top) and Catalyzed DD fusion-fission hybrid (bottom) alternatives with U 2 breeding from Th 22. The Catalyzed DD approach does not contain the Li and T paths. NINREC10-
4 Material Zone Table 1: Fusion-fission reactor geometrical model. Outer Radius (cm) Thickness (cm Remarks Plasma DT(14.06 MeV) or, Catalyzed DD (50 % 2.45 MeV + 50 % MeV) Void Vacuum zone First wall Type 16 stainless steel Water H 2 O cooling channel coolant Structure Molten salt NaF.BeF 2.ThF 4 or: LiF.BeF 2.ThF 4 ρ =4.52 gm/cm ( mol %) Structure Type 16 stainless steel Neutron Graphite as C 12 reflector Structure Type 16 stainless steel Albedo percent albedo surface to simulate neutron and gamma ray reflection Material 1. LiF.BeF 2.ThF 4 salt ρ = 4.52 gm/cm mol % 2. NaF.BeF 2.ThF 4 salt ρ =4.52 gm/cm mol %. Type 16 stainless steel 6.6 wt% Fe, 18 wt% Cr, 1 wt% Ni, 2.6 wt% Mo, 1.9 wt% Mn, 0.9 wt% (Si+Ti+C) ρ = 7.98 gm/cm Table 2: Fusion-fission material compositions. Composition Li 6 Li 7 4Be 9 90Th 20 9F 19 11Na 2 4Be 9 90Th 20 9F 19 C Si Ti Cr Mn Fe Ni Mo Nuclide Density [nuclei/(b.cm)] 1.414x x x x x x x x10-4.7x x x x x x x x x10-4. Graphite C 1.128x10-1 ρ =2.25 gm/cm 5. H 2 O ρ = 1.0 gm/cm H O 6.687x10-2.4x10-2 NINREC10-4
5 Table : Fissile and fusile breeding for sodium and lithium salts in DT and DD symbiotic fusion-fission fuel factories. Blanket thickness = 42 cm, reflector thickness =40 cm; no structure in the salt region. Source Li-Be-Th-F Salt Na-Be-Th-F Salt Li 6 (n,α)t Li 7 (n,n α)t Be 9 (n,t) F(n,T) Total T Th(n,γ) Be 9 (n,t) F(n,T) Total T (Nuclei / fusion source neutron) DD x x x x x10-100% MeV DT 100% MeV Catalyzed DD 50% 2.45 MeV 50% MeV x x x x x x x x x x10 - Th(n,γ) For the catalyzed DD plasma, the Th(n,γ) reaction rate is in the sodium salt compared with 0.77 obtained in the DT system using the lithium salt. For the DT system the tritium production rate is tritium nuclei per source neutron. The tritium production rate is too low to sustain the DT plasma, and an extra supply of the isotope is required to supplement the plasma. This could be internal by allowing some fissions to occur in the blanket supplying extra neutrons, or this could be external in the satellite fission reactors producing the needed difference as a byproduct and feeding it back to the DT plasma. The fissile fuel production rate is higher in the DD system because of the absence of lithium in the salt that would introduce a competition between the Th(n,γ) and the Li 6 (n,t) reactions. 6. USE OF NEUTRON MULTIPLIERS An approach to the fusion-fission hybrid is the fuel factory, where fissile fuel for fission reactors is bred in fusion reactors. In this approach, there is a need to maximize the fissile breeding with the constraint of maintaining self sufficiency in tritium production and realistically accounting for the modeling for structural and coolant compositions and configurations imposed by the thermal hydraulic and mechanical designs. For the DT fusion reaction cycle there appears a need for neutron multiplication using threshold neutron multiplication reactions such as from Pb (Fig. ), Be (Fig. 4), and Bismuth (Fig. 5). Thorium itself in also provides neutron multiplication (Fig. 6). Figure. Neutron multiplication threshold reactions in Pb 206. Source: JENDL. Figure 4. Neutron multiplication threshold reactions in Be 9. Source: JENDL. NINREC10-5
6 the reflector and the lead multiplying-reflecting zone. In the radial blanket, it precedes the reflector. Figure 5. Neutron multiplication threshold reactions in Bi 209. Source: JENDL. Figure 6: The cross section distribution for the (n, 2n) and n( n) neutron multiplication reactions in Th 22 showing energy thresholds at and MeV. Source: JENDL. Figure 7. Laser fusion fissile generator plant with U 2 breeding. 7. THE ENRICHMENT FACTORY APPROACH The direct enrichment approach considers the use of fabricated ThO 2 Light Water Reactor (LWR) fuel assemblies and enriching them in a DT fusion neutron spectrum. Figures 7 and 8 show the reactor configuration using a spherical DT fusion neutron source driven by an inertial confinement system such as a laser, electron or heavy ion beam. The reactor is composed of a right circular cylinder of 6.1 m radius referred to as the radial blanket and two end caps referred to as the axial blanket. The radial blanket is used for both fissile and fusile breeding, whereas the axial blanket is used solely for fusile breeding. The full 4π solid angle is used for neutron multiplication with lead as a neutron multiplier. A 0.25 m lead thickness precedes the axial blanket and reflects a fraction of the neutrons falling on it to the radial blanket. A graphite reflector follows both the axial and radial blankets. Zircaloy-4 is used as a structural material with the composition given in Table 4. Tritium breeding occurs in natural lithium contained in Zircaloy-4 tubes and cooled by sodium. In the axial blanket, the main fusile breeding zone is emplaced between Figure 8. ThO 2 Pressurized Water Reactor fuel elements within the neutron multiplication zone, followed by a tritium breeding zone and a graphite reflector. NINREC10-6
7 8. LEAD FAST FLUX TRAP A lead fast-flux trap is used for fissile breeding, in which LWR reactor ThO 2 fuel assemblies are surrounded by lead from all sides. Between the lead and the assemblies a row of natural lithium tubing is emplaced to achieve a filtering action by absorbing slow neutrons. Maintaining a hard spectrum in the fuel assemblies will avoid the excessive fissioning of the bred U 2. In the lead flux trap, three LWR reactor assemblies are superimposed atop each other around the reactor circumference with a total number of 270. The justification for the use of the flux trap is that due to radiation damage limitations to the first wall, a large cavity of 6.1 m radius is required. If the fuel assembles were positioned side by side around the reactor cavity, this results in a large fertile inventory and a subsequent long time to attain a given average enrichment. However, since the number of neutrons in the system is constant, the use of the flux trap was shown to reduce the fuel inventory and the time to attain a given enrichment at the expense of a slight reduction in the overall fissile fuel production. In a blanket composition not using the flux trap, 2.87 metric tons of U 2 would be produced per year, and the time to attain an average enrichment of 4 percent is.47 years. When the flux trap is used, 2.18 metric tons can be produced yearly, and the time to attain an average 4 percent enrichment is a shorter 2.27 years, together with a reduction in the fuel inventory of 50 percent. reactor to attain an average w/o fissile enrichment in the fuel assemblies (Fig. 11). For a once through LWR cycle, a support ratio of 2- is estimated. However, with fuel recycling, more attractive support ratios of 4-6 may be attainable for a conversion ratio of 0.55, and 5-8 for a conversion ratio of CALCULATIONAL AND GEOMETRICAL MODELS The unit cell shown in Figs. 24 and 25 was developed for the three-dimensional analysis using Monte Carlo particle transport calculations. An albedo surface surrounded the cell, and the source neutrons were sampled isotropically at the lower left edge of the cell as shown in Fig. 24. The material compositions were homogenized according to the volume fractions and compositions of Table 4. The optimization of the fusile and fissile breeding by altering the material thicknesses of the radial and axial blanket regions is shown in Fig. 11. Figure 9. Three dimensional unit cell of computational model of laser fusion hybrid plant. 10. BREEDING IN SOLID FUEL A tritium yield per source neutron of 1.08 and a Th (n, γ) reaction yield of 0.4 can be obtained in the concept where ThO 2 Zircaloy-clad fuel assemblies for Light Water Reactors (LWRs) are enriched in the U 2 isotope by irradiating them in a Pb flux trap. This corresponds to 0.77kg/[MW(th).year] of fissile fuel production, and 1.94 years of irradiation in the fusion Figure 10. Horizontal cut through unit cell of three dimensional computational model. NINREC10-7
8 Table 4: Material compositions and number densities. [19-24]. This allows for the incremental development of the technology for the eventual introduction of a pure fusion technology. Figure 11. Optimization of fissile U 2 and fusile tritium (T) breeding. 9. DISCUSSION The thorium fusion fission hybrid is discussed as a sustainable longer term larger resource base to the fast breeder fission reactor concept. In addition, it offers a manageable waste disposal process, burning of the produced actinides and serious nonproliferation characteristics. With the present day availability of fissile U 25 and Pu 29, and available fusion and accelerator neutron sources, a new look at the thorium-u 2 fuel cycle is warranted. Since no more than 7 percent of the ThO 2 as a breeding seed fuel can be added to a Heavy Water Reactor, HWR before criticality would not be achievable; this suggests that fusion and accelerator sources are the appropriate alternative for the implementation of the Thorium fuel cycle. The use of the thorium cycle in a fusion fission hybrid could bypass the stage of fourth generation breeder reactors in that the energy multiplication in the fission part allows the satisfaction of energy breakeven and the Lawson condition in magnetic and inertial fusion reactor designs A catalyzed or semi-catalyzed DD fusion cycle will not need tritium breeding. Both the DT and Catalyzed DD approaches provide substantial energy amplification through the fusion-fission coupling process. However, the DT system possesses marginal tritium breeding in the fusion island and would need supplemental breeding in the fission satellites to reach a value of the tritium breeding ratio unity [1-4]. As a first generation cycle, a DT fusion cycle needs serious consideration of its tritium breeding potential. Enhancement of the fusile breeding would require the use of neutron multipliers and optimized flux trap geometrical configurations. REFERENCES [1] Magdi Ragheb, Fusion Fission Hybrid as an Early Introduction of Fission and the Thorium Fuel Cycle, i- manager s Journal on Future Engineering & Technology, Vol. 5, No. 1, pp. 1 14, August-October, [2] Magdi Ragheb and Ayman NourElDin, The Fusion- Fission Thorium Hybrid, 1 st Thorium Energy Alliance Conference, The Future Thorium Energy Economy, NINREC10-8
9 Kellog Conference Center, Gallaudet University, Washington D. C , USA, October 19-20, [] Magdi Ragheb and Lefteri Tsoukalas, Global and USA Thorium and Rare Earth Elements Resources, Proceedings of the 2 nd Thorium Energy Alliance Conference, The Future Thorium Energy economy, Google Campus, Mountain View California, USA, March 29-0, [4] M. M. H. Ragheb, R. T. Santoro, J. M. Barnes, and M. J. Saltmarsh, Nuclear Performance of Molten Salt Fusion- Fission Symbiotic Systems for Catalyzed Deuterium and Deuterium-Tritium Reactors, Nuclear Technology, Vol. 48, pp , May [5] M. Ragheb, Optimized Fissile and Fusile Breeding in a Laser-Fusion Fissile-Enrichment Flux Trap Blanket, Journal of Fusion Energy, Vol. 1, No.1, pp , [6] M. M. H. Ragheb, G. A Moses, and C. W. Maynard, Pellet and Pellet-Blanket neutronics and Photonics for Electron Beam Fusion, Nucl. Technol., Vol. 48:16, April [7] M. Ragheb and S. Behtash, Symbiosis of Coupled Systems of Fusion D-He Satellites and Tritium and He Generators, Nuclear Science and Engineering, Vol. 88, pp. 16-6, [8] M. Ragheb and C. W. Maynard, On a Nonproliferation Aspect of the Presence of U 22 in the U 2 fuel cycle, Atomkernenergie, [9] M. M. H. Ragheb, M. Z. Youssef, S. I. Abdel-Khalik, and C. W. Maynard, Three-Dimensional Lattice Calculations for a Laser-Fusion Fissile Enrichment Fuel Factory, Trans. Am. Nucl. Soc., Vol. 0, 59, [10] M. M. H. Ragheb, S. I. Abdel-Khalik, M. Youssef, and C. W. Maynard, Lattice Calculations and Three- Dimensional Effects in a Laser Fusion-Fission Reactor, Nucl. Technol. Vol. 45, 140, [11] H. A. Bethe, The Fusion Hybrid, Nucl. News, Vol. 21, 7, 41, May [12] S. S. Rozhkov and G. E. Shatalov, Thorium in the Blanket of a Hybrid Thermonuclear Reactor, Proc. U.S.-USSR Symp. Fusion-Fission Reactors, July 1-16, 1976, CONF-7607, p. 14, [1] V. L. Blinkin and V. M. Novikov, Symbiotic System of a Fusion and Fission Reactor with Very Simple Fuel Reprocessing, Nucl. Fusion, Vol. 18, 7, [14] Jungmin Kang and Frank N. von Hippel, U-22 and the Proliferation Resistance of U-2 in Spent Fuel, Science and Global Security, Volume 9, pp. 1-2, [15] J. A. Maniscalco, L. F. Hansen, and W. O. Allen, Scoping Studies of U2 breeding fusion fission hybrid, UCRL-80585, Lawrence Livermore Laboratory, [16] L. M. Lidsky, Fission-fusion Systems: Hybrid, Symbiotic and Augean, Nucl. Fusion, Vol. 15, [17] J. D. Lee, The Beryllium/molten salt blanket-a new concept, UCRL-80585, Lawrence Livermore Laboratory, [18] M. M. H. Ragheb and C. W. Maynard, Threedimensional cell calculations for a fusion reactor gascooled solid blanket, Atomkernenergie (ATKE) Bd. 2, Lfg., 159, [19] Terry Kammash, A Promising Approach to Safe, Proliferation Resistant Production of Nuclear Power, Atoms For Peace: an International Journal, Volume 2, Number 4, pp , [20] W. M. Stacey, Georgia Tech Studies of Sub-Critical Advanced Burner Reactors with a D-T Fusion Tokamak Neutron Source for the Transmutation of Spent Nuclear Fuel, J. Fusion Energy, 28:28-, [21] F. Winterberg, Comparison of the recently proposed super-marx generator approach to thermonuclear ignition with the deuterium-tritium laser fusion-fission hybrid concept by the Lawrence Livermore National Laboratory, J. Renewable Sustainable Energy, Volume 1, Issue 5, 0510, [22] Sümer Sahin, Hüseyin Yapici, and Necmettin Sahin, Neutronic Performance of Proliferation Hardened Thorium Fusion Breeders, Fusion Engineering and Design, Volume 54, Issue 1, pp. 6-77, February [2] Joseph Collin Farmer, LIFE Materials: Overview of Fuels and Structural Materials Issues, Volume 1, Lawrence Livermore National Laboratory, LLNL-TR Rev. 1, October 25, [24] Jonathan Fahey, Reinventing Nuclear Power, Forbes Magazine, Technology, April 1, NINREC10-9
The Fusion-Fission Fission Thorium Hybrid
Invited paper presented at the 1st Thorium Energy Alliance Conference, The Future Thorium Energy Economy," Kellog Conference Center, Gallaudet University, Washington D. C. 2002-3695, USA, October 19-20,
More informationOVERVIEW OF THE THORIUM FUEL CYCLE
Paper presented at the Thorium Energy Alliance 7, Critical Metals, Policy and Energy Conference, Palo Alto, California, USA, Stanford Sheraton Hotel, June 3 rd, 4th, 2015. OVERVIEW OF THE THORIUM FUEL
More informationFusion-Fission Hybrid Systems
Fusion-Fission Hybrid Systems Yousry Gohar Argonne National Laboratory 9700 South Cass Avenue, Argonne, IL 60439 Fusion-Fission Hybrids Workshop Gaithersburg, Maryland September 30 - October 2, 2009 Fusion-Fission
More informationSABR FUEL CYCLE ANALYSIS C. M. Sommer, W. Van Rooijen and W. M. Stacey, Georgia Tech
VI. SABR FUEL CYCLE ANALYSIS C. M. Sommer, W. Van Rooijen and W. M. Stacey, Georgia Tech Abstract Various fuel cycles for a sodium cooled, subcritical, fast reactor, SABR 1, with a fusion neutron source
More informationTransmutation of Transuranic Elements and Long Lived Fission Products in Fusion Devices Y. Gohar
Transmutation of Transuranic Elements and Long Lived Fission Products in Fusion Devices Y. Gohar Fusion Power Program Technology Division Argonne National Laboratory 9700 S. Cass Avenue, Argonne, IL 60439,
More informationMolten Salt Reactors: A 2 Fluid Approach to a Practical Closed Cycle Thorium Reactor
Molten Salt Reactors: A 2 Fluid Approach to a Practical Closed Cycle Thorium Reactor Oct 25 th 2007 Presentation to the Ottawa Chapter of the Canadian Nuclear Society Dr. David LeBlanc Physics Department
More informationComparative Analysis of ENDF, JEF & JENDL Data Libraries by Modeling the Fusion-Fission Hybrid System for Minor Actinide Incineration
Comparative Analysis of ENDF, JEF & JENDL Data Libraries by Modeling the Fusion-Fission Hybrid System for Minor Actinide Incineration D. RIDIKAS 1)*, A. PLUKIS 2), R. PLUKIENE 2) 1) DSM/DAPNIA/SPhN, CEA
More information-What is is Thorium Molten-Salt Nuclear Energy Synergetic System: THORIMS-NES?
Thorium Energy Alliance Conference March 29-30, 2010, Mountain View, CA, USA: -What is is Thorium Molten-Salt Nuclear Energy Synergetic System: THORIMS-NES? (Establishing (Establishing SIMPLEST SIMPLEST
More informationNeutronic and Fuel Cycle Consideration: from Single Stream to Two Fluid Th-U Molten Salt System. Olga S. Feinberg
Neutronic and Fuel Cycle Consideration: from Single Stream to Two Fluid Th-U Molten Salt System. Olga S. Feinberg RRC-Kurchatov Institute, 123182, Moscow, RF The History of the Problem In the 60 s and
More informationAbundant and Reliable Energy from Thorium. Kirk Sorensen Flibe Energy UT Energy Week February 17, 2015
Abundant and Reliable Energy from Thorium Kirk Sorensen Flibe Energy UT Energy Week February 17, 2015 This is incorrect. Nuclear energy is our greatest hope for the future. Nuclear energy contains over
More informationThe Nuclear Fuel Cycle Lecture 5
The Nuclear Fuel Cycle Lecture 5 David J. Hamilton d.hamilton@physics.gla.ac.uk 7th February 2011 1. Overview Limitations of thermal recycling of Pu. Fast critical reactors: core physics; breeders; transmutation.
More informationNuclear Energy. Weston M. Stacey Callaway Regents Professor Nuclear and Radiological Engineering Program Georgia Institute of Technology
Nuclear Energy Weston M. Stacey Callaway Regents Professor Nuclear and Radiological Engineering Program Georgia Institute of Technology NAE Symposium The Role of Alternative Energy Sources in a Comprehensive
More informationTRAVELING WAVE REACTOR
TRAVELING WAVE REACTOR M. Ragheb 3/13/2013 INTRODUCTION In the 2012 USA budget, $853 million is allocated for nuclear research, including small reactors. A 30-person Company, TerraPower LLC, at Bellevue,
More informationLecture (3) on. Nuclear Reactors. By Dr. Emad M. Saad. Mechanical Engineering Dept. Faculty of Engineering. Fayoum University
1 Lecture (3) on Nuclear Reactors By Dr. Emad M. Saad Mechanical Engineering Dept. Faculty of Engineering Fayoum University Faculty of Engineering Mechanical Engineering Dept. 2015-2016 2 Nuclear Fission
More informationSpecification for Phase VII Benchmark
Specification for Phase VII Benchmark UO 2 Fuel: Study of spent fuel compositions for long-term disposal John C. Wagner and Georgeta Radulescu (ORNL, USA) November, 2008 1. Introduction The concept of
More informationThe Tube in Tube Two Fluid Approach
The Tube in Tube Two Fluid Approach March 29 th 2010 2 nd Thorium Energy Conference Dr. David LeBlanc Physics Dept, Carleton University, Ottawa & Ottawa Valley Research Associates Ltd. d_leblanc@rogers.com
More informationThe DMSR: Keeping it Simple
The DMSR: Keeping it Simple March 29 th 2010 2 nd Thorium Energy Conference Dr. David LeBlanc Physics Dept, Carleton University, Ottawa & Ottawa Valley Research Associates Ltd. d_leblanc@rogers.com What
More informationMolten-Salt Reactor FUJI and Related Thorium Cycles
Thorium Energy Alliance Spring Conference 2010, March 29-30, 2010, Mountain View, USA 1 Molten-Salt Reactor FUJI and Related Thorium Cycles Ritsuo Yoshioka (Presenter)* K. Furukawa, Y. Kato, K. Mitachi
More informationWM2013 Conference, February 24 28, 2013, Phoenix, Arizona USA
The Potential Role of the Thorium Fuel Cycle in Reducing the Radiotoxicity of Long-Lived Waste 13477 Kevin Hesketh and Mike Thomas The UK s National Nuclear Laboratory, Preston Laboratory, Preston, PR4
More informationOnline Reprocessing Simulation for Thorium-Fueled Molten Salt Breeder Reactor
Online Reprocessing Simulation for Thorium-Fueled Molten Salt Breeder Reactor Andrei Rykhlevskii, Alexander Lindsay, Kathryn Huff Advanced Reactors and Fuel Cycles Group University of Illinois at Urbana-Champaign
More informationINAC-ENFIR Recife, November Molten Salt Nuclear Reactors
INAC-ENFIR Recife, November 24-29 2013 Molten Salt Nuclear Reactors Dr Cassiano R E de Oliveira Department of Chemical and Nuclear Engineering The University of New Mexico cassiano@unm.edu Outline Motivation
More informationInternational Thorium Energy Conference 2015 (ThEC15) BARC, Mumbai, India, October 12-15, 2015
International Thorium Energy Conference 2015 (ThEC15) BARC, Mumbai, India, October 12-15, 2015 Feasibility and Deployment Strategy of Water Cooled Thorium Breeder Reactors Naoyuki Takaki Department of
More informationNOT EVERY HYBRID BECOMES A PRIUS: THE CASE AGAINST THE FUSION-FISSION HYBRID CONCEPT
NOT EVERY HYBRID BECOMES A PRIUS: THE CASE AGAINST THE FUSION-FISSION HYBRID CONCEPT IAP 2010 DON STEINER PROFESSOR EMERITUS,RPI JANUARY 22, 2010 IN 1997 TOYOTA INTRODUCED ITS HYBRID CAR CALLED THE PRIUS
More informationThorium an alternative nuclear fuel cycle
Thorium an alternative nuclear fuel cycle 5th Smart Grids & Clean Power Conference, Cambridge, 5 June 2013 www.cir-strategy.com/events/cleanpower Kevin Hesketh, Senior Research Fellow Outline General Principles
More informationProliferation Risks of Magnetic Fusion Energy
Proliferation Risks of Magnetic Fusion Energy Alexander Glaser* Department of Mechanical and Aerospace Engineering and Woodrow Wilson School of Public and International Affairs Princeton University International
More informationProduction of Rhenium by Transmuting Tungsten Metal in Fast Reactors with Moderator
Journal of Energy and Power Engineering 10 (2016) 159-165 doi: 10.17265/1934-8975/2016.03.003 D DAVID PUBLISHING Production of Rhenium by Transmuting Tungsten Metal in Fast Reactors with Moderator Tsugio
More informationThorium Molten Salt Nuclear Energy Synergetic System (THORIMS-NES)
Thorium Molten Salt Nuclear Energy Synergetic System (THORIMS-NES) Ritsuo Yoshioka (*1), Koshi Mitachi (*1) & Motoyasu Kinoshita(*1,2) (*1) International Thorium Molten-Salt Forum (*2)University of Tokyo
More informationMolten Salt Reactor Technology for Thorium- Fueled Small Reactors
Molten Salt Reactor Technology for Thorium- Fueled Small Reactors Dr. Jess C. Gehin Senior Nuclear R&D Manager Reactor and Nuclear Systems Division gehinjc@ornl.gov, 865-576-5093 Advanced SMR Technology
More informationBreeding Capability of Moltex's Stable Salt Reactor. Naoyuki Takaki, Takumi Iida Department of Nuclear Safety Engineering
Breeding Capability of Moltex's Stable Salt Reactor Naoyuki Takaki, Takumi Iida Department of Nuclear Safety Engineering Contents Recent movement in Japan Why breeder? Moltex s Stable Salt Reactor Pin
More informationHydrogen isotopes permeation in a fluoride molten salt for nuclear fusion blanket
J. Plasma Fusion Res. SERIES, Vol. (5) Hydrogen isotopes permeation in a fluoride molten salt for nuclear fusion blanket Akira Nakamura, Satoshi Fukada and Ryosuke Nishiumi Department of Advanced Energy
More informationAN INVESTIGATION OF TRU RECYCLING WITH VARIOUS NEUTRON SPECTRUMS
AN INVESTIGATION OF TRU RECYCLING WITH VARIOUS NEUTRON SPECTRUMS Yong-Nam Kim, Hong-Chul Kim, Chi-Young Han and Jong-Kyung Kim Hanyang University, South Korea Won-Seok Park Korea Atomic Energy Research
More informationFlexibility of the Gas Cooled Fast Reactor to Meet the Requirements of the 21 st Century
Flexibility of the Gas Cooled Fast Reactor to Meet the Requirements of the 21 st Century T D Newton and P J Smith Serco Assurance (Sponsored by BNFL) Winfrith, Dorset, England, DT2 8ZE Telephone : (44)
More informationComparison of characteristics of fast and thermal reactors, Role of fast reactors in Indian Nuclear Programme
Comparison of characteristics of fast and thermal reactors, Role of fast reactors in Indian Nuclear Programme K.S. Rajan Professor, School of Chemical & Biotechnology SASTRA University Joint Initiative
More informationDisposing High-level Transuranic Waste in Subcritical Reactors
Disposing High-level Transuranic Waste in Subcritical Reactors Yaosong Shen Institute of Applied Physics and Computational Mathematics, 6 Huayuan Road, 100088, Beijing, China We propose a new method of
More informationFission-Suppressed Fusion Breeder on the Thorium Cycle and Nonproliferation
Vallecitos Molten Salt Research Report No. 4 (2011) September 14, 2011 Fission-Suppressed Fusion Breeder on the Thorium Cycle and Nonproliferation R. W. Moir Vallecitos Molten Salt Research, 607 E. Vallecitos
More informationAnalysis of Technical Issues for Development of Fusion-Fission Hybrid Reactor (FFHR)
Analysis of Technical Issues for Development of Fusion-Fission Hybrid Reactor (FFHR) Doo-Hee Chang Nuclear Fusion Technology Development Division, Korea Atomic Energy Research Institute, Daejeon 34057,
More informationThorium for Nuclear Energy a Proliferation Risk?
Thorium for Nuclear Energy a Proliferation Risk? Wolfgang Rosenstock and Olaf Schumann Fraunhofer-Institut für Naturwissenschaftlich- Technische Trendanalysen (INT) Euskirchen, Germany Department Nuclear
More informationSpecification for Phase IID Benchmark. A. BARREAU (CEA, France) J. GULLIFORD (BNFL, UK) J.C. WAGNER (ORNL, USA)
Specification for Phase IID Benchmark PWR-UO 2 Assembly: Study of control rods effects on spent fuel composition A. BARREAU (CEA, France) J. GULLIFORD (BNFL, UK) J.C. WAGNER (ORNL, USA) 1. Introduction
More informationLiquid Blankets & Fusion-Fission
Liquid Blankets & Fusion-Fission Hybrids Fusion-Fission Research Workshop Sept. 30, 2009 Gaithersburg, Md G. A. Wurden LA-UR-09-06268 Abstract This talk is a short overview/review. A variety of fusion
More informationAEN WPRS Sodium Fast Reactor Core Definitions (version 1.2 September 19 th )
AEN WPRS Sodium Fast Reactor Core Definitions (version 1.2 September 19 th ) David BLANCHET, Laurent BUIRON, Nicolas STAUFF CEA Cadarache Email: laurent.buiron@cea.fr 1. Introduction and main objectives
More informationENCAPSULATED NUCLEAR HEAT SOURCE REACTORS FOR ENERGY SECURITY
15 th Pacific Basin Nuclear Conference, Sidney, Australia, October 15-20, 2006 ENCAPSULATED NUCLEAR HEAT SOURCE REACTORS FOR ENERGY SECURITY Greenspan E 1., Hong S.G. 1,2, Monti L 1,3., Okawa T 1,4., Sumini
More informationBurn up Analysis for Fuel Assembly Unit in a Pressurized Heavy Water CANDU Reactor
Burn up Analysis for Fuel Assembly Unit in a Pressurized Heavy Water CANDU Reactor A. A. EL-Khawlani a, Moustafa Aziz b, M. Ismail c and A. Y. Ellithi c a Physics Department, Faculty of Science, High Education,
More informationNuclear Fuel Cycle Lecture 8: Reactor Concepts
Nuclear Fuel Cycle 2011 Lecture 8: Reactor Concepts Fission Exotherm process for all nuclides with more than 130 nucleons (A>130) Activation energy for A=130 is very high; 100 MeV For A > 230 the activation
More informationWorkshop on PR&PP Evaluation Methodology for Gen IV Nuclear Energy Systems. Tokyo, Japan 22 February, Presented at
PR&PP Collaborative Study with GIF System Steering Committees A Compilation of Design Information and Crosscutting Issues Related to PR&PP Characterization Presented at Workshop on PR&PP Evaluation Methodology
More informationEconomic Evaluation of Electrical Power Generation Using Laser Inertial Fusion Energy (LIFE)
Economic Evaluation of Electrical Power Generation Using Laser Inertial Fusion Energy (LIFE) TM Anklam, Wayne Meier, Al Erlandson, Robin Miles, Aaron Simon Lawrence Livermore National Laboratory Submitted
More informationEM 2 : Nuclear Power for the 21 st Century
EM 2 : Nuclear Power for the 21 st Century Presented at the Canon Institute for Global Studies Climate Change Symposium Climate Change and the Role of Nuclear Energy By Dr. Christina Back February 5, 2016
More informationTHE CASE FOR FUSION-FISSION HYBRIDS ENABLING SUSTAINABLE NUCLEAR POWER WESTON M STACEY GEORGIA TECH JANUARY 22, 2010
THE CASE FOR FUSION-FISSION HYBRIDS ENABLING SUSTAINABLE NUCLEAR POWER WESTON M STACEY GEORGIA TECH JANUARY 22, 2010 SUSTAINABLE NUCLEAR POWER Sustainable nuclear power requires closing the nuclear fuel
More informationThorium and Uranium s Mutual Symbiosis: The Denatured Molten Salt Reactor DMSR
Thorium and Uranium s Mutual Symbiosis: The Denatured Molten Salt Reactor DMSR Dr. David LeBlanc Physics Dept, Carleton University, Ottawa & Ottawa Valley Research Associates Ltd. d_leblanc@rogers.com
More informationCalculation of Pellet Radial Power Distributions with Monte Carlo and Deterministic Codes
Progress in NUCLEAR SCIENCE and TECHNOLOGY, Vol. 2, pp.301-305 (2011) TECHNICAL MATERIAL Calculation of Pellet Radial Power Distributions with Monte Carlo and Deterministic Codes Motomu SUZUKI *, Toru
More informationTrends in Transmutation Performance and Safety Parameters Versus TRU Conversion Ratio of Sodium-Cooled Fast Reactors
Trends in Transmutation Performance and Safety Parameters Versus TRU Conversion Ratio of Sodium-Cooled Fast Reactors The Tenth OECD Nuclear Energy Agency Information Exchange Meeting on Actinide and Fission
More informationImproving Conversion Ratio of PWR with Th-U 233 Fuel Using Boiling Channels
67 Reactor Physics and Technology I (Wednesday, February 12, 2014 11:30) Improving Conversion Ratio of PWR with Th-U 233 Fuel Using Boiling Channels M. Margulis, E. Shwageraus Ben-Gurion University of
More informationONCE-THROUGH THORIUM FUEL CYCLE OPTIONS FOR THE ADVANCED PWR CORE
ONCE-THROUGH THORIUM FUEL CYCLE OPTIONS FOR THE ADVANCED PWR CORE Myung-Hyun Kim and Il-Tak Woo Department of Nuclear Engineering Kyung Hee University YoungIn, KyungGi-Do, 449-701, Korea mhkim@nms.kyunghee.ac.kr;
More informationTHE PROMISE OF FUSION ENERGY. General Atomics
THE PROMISE OF FUSION ENERGY General Atomics The following slide show is a compilation of slides from many previous similar slide shows that have been produced by different members of the fusion and plasma
More informationTHORIUM FUEL OPTIONS FOR SUSTAINED TRANSURANIC BURNING IN PRESSURIZED WATER REACTORS
THORIUM FUEL OPTIONS FOR SUSTAINED TRANSURANIC BURNING IN PRESSURIZED WATER REACTORS - 12381 Fariz Abdul Rahman*, Fausto Franceschini**, Michael Wenner**, John C. Lee* *University of Michigan, Ann Arbor,
More informationBenchmark Specification for HTGR Fuel Element Depletion. Mark D. DeHart Nuclear Science and Technology Division Oak Ridge National Laboratory
I. Introduction Benchmark Specification for HTGR Fuel Element Depletion Mark D. DeHart Nuclear Science and Technology Division Oak Ridge National Laboratory Anthony P. Ulses Office of Research U.S. Nuclear
More informationSystematic Evaluation of Uranium Utilization in Nuclear Systems
Systematic Evaluation of Uranium Utilization in Nuclear Systems Taek K. Kim and T. A. Taiwo 11 th Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation San Francisco,
More informationRecent Research Activities on Thorium and MSR in Japan
Recent Research Activities on Thorium and MSR in Japan Takashi Kamei Research Institute for Applied Sciences, Researcher 49, Tanaka-Oi-cho, Sakyo-ku, Kyoto, 606-8202, JAPAN E-Mail: hae00675@nifty.com Introduction
More informationAnalysis of Core Physics Test Data and Sodium Void Reactivity Worth Calculation for MONJU Core with ARCADIAN-FBR Computer Code System
FR09 - International Conference on Fast Reactors and Related Fuel Cycles Analysis of Core Physics Test Data and Sodium Void Reactivity Worth Calculation for MONJU Core with ARCADIAN-FBR Computer Code System
More information2017 Water Reactor Fuel Performance Meeting September 10 (Sun) ~ 14 (Thu), 2017 Ramada Plaza Jeju Jeju Island, Korea
NEUTRONIC ANALYSIS OF THE CANDIDATE MULTI-LAYER CLADDING MATERIALS WITH ENHANCED ACCIDENT TOLERANCE FOR VVER REACTORS Ondřej Novák 1, Martin Ševeček 1,2 1 Department of Nuclear Reactors, Faculty of Nuclear
More informationDesign and Safety Aspect of Lead and Lead-Bismuth Cooled Long-Life Small Safe Fast Reactors for Various Core Configurations
Journal of NUCLEAR SCIENCE and TECHNOLOGY, 32[9], pp. 834-845 (September 1995). Design and Safety Aspect of Lead and Lead-Bismuth Cooled Long-Life Small Safe Fast Reactors for Various Core Configurations
More informationApplication of CANDLE Burnup to Block-Type High Temperature Gas Cooled Reactor for Incinerating Weapon Grade Plutonium
GENES4/ANP2003, Sep. 15-19, 2003, Kyoto, JAPAN Paper 1079 Application of CANDLE Burnup to Block-Type High Temperature Gas Cooled Reactor for Incinerating Weapon Grade Plutonium Yasunori Ohoka * and Hiroshi
More informationIrradiation of Metallic Fuels With Rare Earth Additions for Actinide Transmutation in the ATR Experiment Description for AFC-2A and AFC-2B
INL/EXT-06-11707 Irradiation of Metallic Fuels With Rare Earth Additions for Actinide Transmutation in the ATR Experiment Description for AFC-2A and AFC-2B S.L. Hayes T.A. Hyde W.J. Carmack November 2006
More informationChapter 7: Strategic roadmap
Chapter 7: Strategic roadmap Research is to see what everybody else has seen, and to think what nobody else has thought. ~ Albert Szent-Gyorgyi~ Overview A systematic strategic thorium-based fuel implementation
More informationWe are IntechOpen, the world s leading publisher of Open Access books Built by scientists, for scientists. International authors and editors
We are IntechOpen, the world s leading publisher of Open Access books Built by scientists, for scientists 3,500 108,000 1.7 M Open access books available International authors and editors Downloads Our
More informationWe are IntechOpen, the world s leading publisher of Open Access books Built by scientists, for scientists. International authors and editors
We are IntechOpen, the world s leading publisher of Open Access books Built by scientists, for scientists 4,100 116,000 120M Open access books available International authors and editors Downloads Our
More informationVariations in Neutronic Characteristics Accompanying Burnup in a Large Fast Converter
journal of NUCLEAR SCIENCE and TECHNOLOGY, 7 (7), p. 341-354 (July 1970), 341 Variations in Neutronic Characteristics Accompanying Burnup in a Large Fast Converter Shizuo YAMASHITA* Received October 29,
More informationFast Molten Salt Reactor with U-Pu Fuel
Fast Molten Salt Reactor with U-Pu Fuel L.I. Ponomarev A.A.Bochvar High Technology Research Institute of Inorganic Materials, Moscow Problems of the contemporary nuclear power Preferences of molten salt
More informationCritique of The Future of the Nuclear Fuel Cycle: An Interdisciplinary MIT Study (2011)
Critique of The Future of the Nuclear Fuel Cycle: An Interdisciplinary MIT Study (2011) Developed by the Science Council for Global Initiative Contact: Tom Blees 1. The Study
More informationFast and High Temperature Reactors for Improved Thermal Efficiency and Radioactive Waste Management
What s New in Power Reactor Technologies, Cogeneration and the Fuel Cycle Back End? A Side Event in the 58th General Conference, 24 Sept 2014 Fast and High Temperature Reactors for Improved Thermal Efficiency
More informationBhabha Atomic Research Centre
Bhabha Atomic Research Centre Department of Atomic Energy Mumbai, INDIA An Acrylic Model of AHWR to Scale 1:50 Threat of climate change and importance of sustainable development has brought nuclear power
More informationACTINIDE COMPOSITION ANALYSIS OF LIGHT WATER REACTOR (LWR) FOR DIFFERENT REACTOR CONDITION OF BURNUP AND COOLING TIME
ACTINIDE COMPOSITION ANALYSIS OF LIGHT WATER REACTOR (LWR) FOR DIFFERENT REACTOR CONDITION OF BURNUP AND COOLING TIME Sidik Permana 1, Abdul Waris 1, Mitsutoshi Suzuki 2 and Masako Saito 3 1 Department
More informationChemical Engineering 412
Chemical Engineering 412 Introductory Nuclear Engineering Lecture 20 Nuclear Power Plants II Nuclear Power Plants: Gen IV Reactors Spiritual Thought 2 Typical PWR Specs Reactor Core Fuel Assembly Steam
More informationTutorial Principles and Rationale of the Fusion-Fission Hybrid Burner Reactor. Weston M. Stacey Georgia Institute of Technology Atlanta, GA USA
Tutorial Principles and Rationale of the Fusion-Fission Hybrid Burner Reactor Weston M. Stacey Georgia Institute of Technology Atlanta, GA 30332 USA (Presented at FUNFI-2011 Workshop Fusion for Neutrons
More informationThe role of thorium in UK nuclear R&D
The role of thorium in UK nuclear R&D Current trends and MSFR modelling 28 th October 2013, ThEC 2013, CERN The role of thorium in UK nuclear R&D Analysis of UK nuclear R&D strategy. The role of fuel cycle
More informationFull Submersion Criticality Accident Mitigation in the Carbide LEU-NTR
Full Submersion Criticality Accident Mitigation in the Carbide LEU-NTR Paolo Venneri, Yonghee Kim Advanced Institute of Science and Technology, 291 Daehak-ro, Yuseong-gu, Daejeon, Korea, 35-71 paolovenneri@kaist.ac.kr,
More informationNuclear Power Generation Past, Present & Future
Nuclear Power Generation Past, Present & Future Brett Edmonds Halesworth U3A Science Group - 24 November 2016 Overview of Nuclear Power Technology Core generation technology same as fossil fuel powered
More informationTransmutation. Janne Wallenius Professor Reactor Physics, KTH. ACSEPT workshop, Lisbon
Transmutation Janne Wallenius Professor Reactor Physics, KTH Why would one want to transmute high level nuclear waste? Partitioning and transmutation of Pu, Am & Cm reduces the radio-toxic inventory of
More informationOn the Practical Use of Lightbridge Thorium-based Fuels for Nuclear Power Generation
On the Practical Use of Lightbridge Thorium-based Fuels for Nuclear Power Generation Revision 1 - July 2010 Lightbridge Corporation 1600 Tysons Blvd. Suite 550 Mclean, VA 22102 USA P +1 571.730.1200 F
More informationADVANCED OPTIONS FOR TRANSMUTATION STRATEGIES. M. Salvatores CEA-DRN Bât. 707 CE/Cadarache Saint-Paul-Lez-Durance Cedex France.
ADVANCED OPTIONS FOR TRANSMUTATION STRATEGIES M. Salvatores CEA-DRN Bât. 707 CE/Cadarache 13108 Saint-Paul-Lez-Durance Cedex France Abstract Advanced options for transmutation strategies currently investigated
More informationThe Thorium Fuel Cycle
The Thorium Fuel Cycle ThEC13 Daniel Mathers daniel.p.mathers@nnl.co.uk Outline Content: Background Sustainability, proliferation resistance, economics, radiotoxicity Advantages and disadvantages Fuel
More informationUCSD-ENG-0083 THE ARIES FUSION NEUTRON-SOURCE STUDY
UCSD-ENG-0083 THE ARIES FUSION NEUTRON-SOURCE STUDY D. Steiner, E. Cheng, R. Miller, D. Petti, M. Tillack, L. Waganer and the ARIES Team August 2000 1. Introduction Last year the ARIES team initiated the
More informationTypes of Nuclear Reactors. Dr. GUVEN Professor of Aerospace Engineering Nuclear Science and Technology Engineer
Types of Nuclear Reactors Dr. GUVEN Professor of Aerospace Engineering Nuclear Science and Technology Engineer Types of Reactors (Fuel) As far as the type of fuels are concerned, three types of reactors
More informationInfluence of Fuel Design and Reactor Operation on Spent Fuel Management
Influence of Fuel Design and Reactor Operation on Spent Fuel Management International Conference on The Management of Spent Fuel from Nuclear Power Reactors 18 June 2015 Vienna, Austria Man-Sung Yim Department
More informationLOS ALAMOS AQUEOUS TARGET/BLANKET SYSTEM DESIGN FOR THE ACCELERATOR TRANSMUTATION OF WASTE CONCEPT
LOS ALAMOS AQUEOUS TARGET/BLANKET SYSTEM DESIGN FOR THE ACCELERATOR TRANSMUTATION OF WASTE CONCEPT M. Cappiello, J. Ireland, J. Sapir, and B. Krohn Reactor Design and Analysis Group Los Alamos National
More informationCurrent Situation of MSR Development in Japan. Yoichiro SHIMAZU Graduate School of Engineering Hokkaido University, Japan
Current Situation of MSR Development in Japan Yoichiro SHIMAZU Graduate School of Engineering Hokkaido University, Japan 1 Related Organizations International Thorium Molten-Salt Forum (ITHMSF ) President:
More informationTHE NUCLEAR FUEL CYCLE
THE NUCLEAR FUEL CYCLE Uranium is a slightly radioactive metal that is found throughout the earth s crust It is about 500 times more abundant than gold and about as common as tin Natural uranium is a mixture
More informationPARAMETRIC STUDY OF THERMO-MECHANICAL BEHAVIOUR OF 19- ELEMENT PHWR FUEL BUNDLE HAVING AHWR FUEL MATERIAL
PARAMETRIC STUDY OF THERMO-MECHANICAL BEHAVIOUR OF 19- ELEMENT PHWR FUEL BUNDLE HAVING AHWR FUEL MATERIAL R. M. Tripathi *, P. N. Prasad, Ashok Chauhan Fuel Cycle Management & Safeguards, Directorate of
More informationNuclear Power Plants (NPPs)
(NPPs) Laboratory for Reactor Physics and Systems Behaviour Weeks 1 & 2: Introduction, nuclear physics basics, fission, nuclear reactors Critical size, nuclear fuel cycles, NPPs (CROCUS visit) Week 3:
More informationNeutronic Feasibility of a Breed & Burn Molten Salt Reactor
Neutronic Feasibility of a Breed & Burn Molten Salt Reactor A. KASAM, E. S HWAGERAUS Serpent User Group Meeting 206 - Milan 26-29 September, 206 Objectives. Demonstrate possibility of breed & burn operation
More informationMONTE CARLO CALCULATIONS ON THE FIRST CRITICALITY OF THE MULTIPURPOSE REACTOR G.A. SIWABESSY. Liem Peng Hong Center for Multipurpose Reactor - BATAN
MONTE CARLO CALCULATIONS ON THE FIRST CRITICALITY OF THE MULTIPURPOSE REACTOR G.A. SIWASSY Liem Peng Hong Center for Multipurpose Reactor - BATAN ABSTCT MONTE CARLO CALCULATIONS ON THE FIRST CRITICALITY
More informationFBNR Letter FIXED BED NUCLEAR REACTOR FBNR
FBNR Letter FIXED BED NUCLEAR REACTOR FBNR http://www.rcgg.ufrgs.br/fbnr.htm Farhang.Sefidvash@ufrgs.br Dear coworkers and potential coworkers around the world, As number of coworkers is increasing, we
More informationModule 12 Generation IV Nuclear Power Plants. Atominstitute of the Austrian Universities Stadionallee 2, 1020 Vienna, Austria
Module 12 Generation IV Nuclear Power Plants Prof.Dr. H. Böck Atominstitute of the Austrian Universities Stadionallee 2, 1020 Vienna, Austria boeck@ati.ac.at Generation IV Participants Evolution of Nuclear
More informationThe role of Thorium for facilitating large scale deployment of nuclear energy
The role of Thorium for facilitating large scale deployment of nuclear energy R.K. Sinha Chairman, Atomic Energy Commission Government of India IAEA International Ministerial Conference on Nuclear Power
More informationTHE USE OF THORIUM IN NUCLEAR POWER REACTORS JUNE 1969
WASH 1097 UC-80 THE USE OF THORIUM IN NUCLEAR POWER REACTORS JUNE 1969 PREPARED BY Brookhaven National Laboratory AND THE Division of Reactor Development and Technology WITH THE ASSISTANCE OF ARGONNE NATIONAL
More informationAugust 24, 2011 Presentation to Colorado School of Mines
HEAVY-METAL NUCLEAR POWER: Could Reactors Burn Radioactive Waste to Produce Electric Power and Hydrogen? Eric P. Loewen, Ph.D. President, American Nuclear Society August 24, 2011 Presentation to Colorado
More informationSubcritical Experiments in Uranium-Fueled Core with Central Test Zone of Tungsten
PHYSOR 2004 -The Physics of Fuel Cycles and Advanced Nuclear Systems: Global Developments Chicago, Illinois, April 25-29, 2004, on CD-ROM, American Nuclear Society, Lagrange Park, IL. (2004) Subcritical
More informationUNIT-5 NUCLEAR POWER PLANT. Joining of light nuclei Is not a chain reaction. Cannot be controlled
UNIT-5 NUCLEAR POWER PLANT Introduction Nuclear Energy: Nuclear energy is the energy trapped inside each atom. Heavy atoms are unstable and undergo nuclear reactions. Nuclear reactions are of two types
More informationA HELIUM COOLED PARTICLE FUEL REACTOR FOR FUEL SUSTAINABILITY. T D Newton, P J Smith and Y Askan SERCO Assurance, Winfrith, Dorset, England * Abstract
A HELIUM COOLED PARTICLE FUEL REACTOR FOR FUEL SUSTAINABILITY T D Newton, P J Smith and Y Askan SERCO Assurance, Winfrith, Dorset, England * Abstract Sustainability is a key goal for future reactor systems.
More informationToroidal Reactor Designs as a Function of Aspect Ratio
Toroidal Reactor Designs as a Function of C.P.C. Wong ), J.C. Wesley ), R.D. Stambaugh ), E.T. Cheng ) ) General Atomics, San Diego, California ) TSI Research Inc., Solana Beach, California e-mail contact
More information